ML18102B554

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Semi-Annual Radioactive Effluent Release Rept.
ML18102B554
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/30/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML18102B553 List:
References
RERR-42, NUDOCS 9709030146
Download: ML18102B554 (39)
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Text

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.. PDR' . . SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 AUGUST, 1997 l I I .. I I I I I I I I I SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-42 SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 AUGUST, 1997 I I .. I I I I I I

  • I I I I I I :. I SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -JUNE 1997 Table of Contents INTRODUCTION PART A. 1. 0 2. 0 3.0 4.0 5.0 6.0 7.0 8. 0 PART B . PART C. PART D. PART E. PART F. PART G. PART H. PRELIMINARY SUPPLEMENTAL INFORMATION REGULATORY LIMITS .................................. . 1.1 Fission and Activation Gas Release Limits ..... . 1.2 Iodine Particulates, and Tritium .............. . 1.3 Liquid Effluents Release Limits ............... . 1. 4 Total Dose Limit .............................. . MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) ........... . AVERAGE ENERGY ..................................... . MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY

...................................... . BATCH RELEASES ..................................... . UNPLANNED RELEASES ................................. . ELEVATED RADIATION MONITOR RESPONSES

............... . MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT 3 3 3 3 4 4 4 5 5 7 7 7 RELEASE REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Amendement to RERR-41 ...............................

31 GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

7 Summation Table lAl -Unit 1 ........................

12 Summation Table 1A2 -Unit 2 ........................

13 Summation Table lBl -Unit 1 ........................

14 Summation Table 1B2 -Unit 2 ........................

15 Gaseous Effluent -Ground Level Releases ............

16 LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

7 Summa ti on Table 2A-1 Unit 1 .........................

1 7 Summation Table 2A-2 Unit 2 .........................

18 Summation Table 2B-1 Unit 1 .........................

19 Summation Table 2B-2 Unit 2 .........................

20 Summary Tables 4A-1 and 4A-2 .....................

23-30 SOLID WASTE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

7 Summation Table -Units 1 and 2 ..................

21-22 RADIOLOGICAL IMPACT ON MAN . * * * * * * * * * * . * . * * * . . . * * * . . . 8 Liquid Pathways ....................

. . . . . . . . . . . . . . . . 8 Air Pathways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Direct Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Assessment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 METEOROLOGICAL DATA .................................

10 ODCM CHANGES .......................................

10 INOPERABLE MONITORS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 O ii I I PART I PART PART I I I I I I I I I I I I I I . J. K. SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -JUNE 1997 Table of Contents (Cont'd) PROCESS CONTROL PROGRAM (PCP) CHANGES ...............

11 ENVIRONMENTAL MONITORING LOCATION CHANGES ...........

11 MAJOR CHANGES TO WASTE PROCESSING SYSTEMS ...........

11 iii I I I I I I I I I I I I I I INTRODUCTION SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -JUNE 1997 This report, SGS-RERR-42, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station (SGS) Units 1 and 2 for the period January 1, 1997 to June 30, 1997. This Semiannual RERR is submitted for both Salem Units and combines those sections which are common to each unit. Separate tables of releases and release totals are included whenever separate processing systems exist. Salem Unit 1 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3338 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 1 achieved initial criticality on December 11, 1976 and went into commercial operations on June 30, 1977. Salem Unit 2 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3338 MWt and an approximate net electrical output of 1115 MWe. Salem Unit 2 achieved initial criticality on August 2, 1980 and went into commercial operations on October 13, 1981. The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.8 of the Salem Technical Specifications.

Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments and our responses to parts A-F of the "Supplemental Information

section of Regulatory Guide 1.21, Appendix B. As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary description of how measurements and determinations of the total activity discharged were developed.

1 I I -I I I I I I I I I I I I I To facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.

Unit 1 generated 0 megawatt-hours of electrical energy (net) during the reporting period. Unit 2 generated 0 megawatt-hours of electrical energy (net) during the reporting period. Results of liquid and gaseous composites analyzed for Sr-89, Sr-90 and Fe-55 for the second quarter of 1997 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release Report. The Sr-89, Sr-90 and Fe-55 analyses for the fourth quarter of 1996 (refer to RERR-41) have been completed; amended pages to RERR-41 are included in this report. 2 I . I -I I I I I I

  • I I I I I I PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin. In addition, the air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the site boundary, shall be limited to the following:

During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation . 1.2 Iodine, Particulates, and Tritium The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

For Iodine-131, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. In addition, the dose to a member of the public from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the site boundary, shall be limited to the following:

During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and During any calendar year: Less than or equal to 15 mrems to any organ. 3 I I I I I I I I I I I I I I I 1.3 Liquid Effluents Release Limits 1. 4 The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.

In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited: During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ. Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems). 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) Regulatory Guide 1.21 requires that the licensee provide the MPCs used in determining allowable release rates for radioactive releases.

a. b. c. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.

MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids. The MPC value used for dissolved or entrained noble gases is 2E-4 microcuries per milliliter.

4 I I I I I I I I I I I I I I I 3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.

Release limits for SGS are not based upon average energy, hence, this section does not apply. 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid effluents are monitored in accordance with Table 4.11-1 of the Technical Specifications.

During the period of record, all batch liquid wastes from the chemical drain tank and the laundry and hot shower tanks were routed to the hold-up tanks for monitoring prior to release. Technical Specifications require these tanks to be uniformly mixed for sampling and analysis before being released.

Batch releases are defined as releases from the waste monitor hold-up tank and the chemical and volume control tanks. Continuous liquid releases are defined as condensate releases from intermittent blowdown of the steam generators.

Specific activities from analyses were multiplied by the volume of effluent discharged to the environment in order to estimate the total liquid activity discharged.

The detection requirements of Tables 4.11-1 of the Technical Specifications are achieved or exceeded.

Radionuclides detected at concentrations below the Technical Specification detection limits (LLDs) are treated as being present. Radionuclides for which no activity was detected, while meeting the required LLDs, are treated as absent. 4.2 Gaseous Effluents Gaseous effluent streams are monitored and sampled in accordance with Table 4.11-2 of the Technical Specifications.

The plant vent is the final release point of all planned gaseous effluents and is continuously monitored by beta scintillator and high range GM tubes. The vent is also continuously sampled for iodine and particulates with a charcoal cartridge and filter paper. The filter and charcoal are changed weekly, and analyzed on a multi-channel analyzer in the laboratory.

5 I I I I I I I I I I I I I I Noble gas sampling is also performed on all gas decay tanks and containment purges prior to their release to the environment.

The plant vent is sampled weekly for noble gases. The detection requirements of Tables 4.11-1 and 4.11-2 of the Technical Specifications are achieved or exceeded.

Radionuclides detected at concentrations below the Technical Specification detection limits (LLDs) are treated as being present. Radionuclides for which no activity was detected, while meeting the required LLDs, are treated as absent. Continuous Mode gaseous releases are quantified by routine (monthly or weekly) sampling and isotopic analyses of the plant vent. Specific activities for each isotope detected are multiplied by the total vent flow volume for the entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent. Slightly elevated plant vent radiation monitor readings are treated as continuous.

releases.

The monitors response is converted to a "specific activity" using historical efficiency factors. The "specific activity" is multiplied by a default volume of effluent discharge to estimate the total activity discharged.

Batch Mode gaseous releases are quantified by sampling each gas decay tank or containment purge prior to discharge.

Specific activities for each isotope are multiplied by the total volume of gas discharged for that batch. Elevated plant vent radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases.

If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors.

The monitors response is converted to a "specific activity" using historical efficiency factors. The "specific activity" is multiplied by the volume of effluent discharged while the channel was in an alarm state in order to estimate the total activity discharged.

6 I I I I I I I I I I I I 4.3 Estimated Total Error 5.0 The estimated total error of reported liquid and solid releases is within 25% The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 10%. Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are not defined. BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-l and 4B-l for Unit 1 and 4A-2 and 4B-2 for Unit 2. 6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.

7.0 ELEVATED PLANT VENT CHANNEL RESPONSES During this reporting period, there were no elevated monitor readings on Salem Unit 1/2 Plant Vent Radiation Monitors.

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-41) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the fourth quarter of 1996. PART B. GASEOUS EFFLUENTS See Summary Tables lA-1 thru lC for Salem Unit 1 Operations.

See Summary Tables lA-2 thru lC for Salem Unit 2 Operations.

I PART c. LIQUID EFFLUENTS I See Summary Tables 2A-l thru 2B for Salem Unit 1 Operations.

See Summary Tables 2A-2 thru 2B for Salem Unit 2 Operations.

PART D. SOLID WASTE See Summary in Table 3. 7 I I I I I I I I

  • I I I I I I :. I PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on the controlling dose pathways and age groups as described below. The estimated dose represents the maximum radiation dose that could be received by a member of the general public. The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting interval.

Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual. Liquid Pathways (Units 1 & 2) Type Age Group Location Total Body Organ Dose Adult Adult Total Body Organ (GI-LLI) ------Site Boundary Site Boundary 0.081 mrem 0.138 mrem Air Pathways (Units 1 & 2) Age Group Location Pathway Seafood Ingestion Seafood Ingestion Limit 3 mrem 10 mrem Pathway Total Body Skin Organ All All Teenager Site Boundary Site Boundary Site Boundary Direct Exposure Direct Exposure Inhalation Dose Total Body Skin Organ (Lung) --------O.OOE+O mrem O.OOE+O mrem 6.54E-2 mrem 8 Limit 500 mrem/yr 3000 mrem/yr 10 mrem I I ,, I I I I I I

  • I I I I I I I Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.

One method for comparing TLD measurements is by comparison with preoperational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, as well as natural background radiation.

TLD data for the six month reporting period is given below: TLD 2S-2 5S-l Location 0.3 mile 0.9 mile 4. 3 3.5 Measurement mrad/month mrad/month These values are interpreted to represent natural background.

They are within the statistical variation associated with the pre-operational program results, which are: 3.7 mrad/month for location 2S-2, and 4.2 mrad/month for location 5S-l. Assessment Salem Units 1 and 2 were shutdown during the entire reporting period for extended maintenance and repair. Gaseous and liquid effluents released from Salem station resulted in a minimal dose to the maximum hypothetical individual.

All radioactive releases from Salem station during this reporting period were well within all Federal limits. The following two trend graphs show the total curies of gaseous and liquid effluents released from Salem Units 1 and 2 for the past 5 years. Calculated doses in the graphs are to the maximum hypothetical individual.

() c: iii' "' Q 3 ;; 3 Salem Unit 1 and 2 Gaseous Effluents Noble Gas Curies Released and Calculated Dose Note : Calculated doses are to the maximum hypothetical individual 1.00E+OJ 1.00E+OO 1.00E-03 1.00E-06 1.00E-09 1992 1993 1994 1995 1996 1997 Reporting Period 9

_._TB ------*-----

I I ,. I I I I I I

  • I I I I I I :. I PART F. PART G. PART H. ("') c: ;;;* rn Q 3 .. 3 Salem Units 1 and 2 Liquid Effluents Curies Released and Calculated Doses Note: Calculated doses are to the maximum hypothetical individual 10 0.1 0.01 1992 1993 1994 1995 1996 1997 Reporting Period i.=+--cuRIE:si l---o---ORGAN ; I METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation will be provided in the next RERR report (RERR-43)

OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this period, there were no revisions to the SGS Off-Site Dose Calculation Manual. INOPERABLE MONITORS During this period, the following effluent monitors were inoperable for more than 30 days:

  • Salem Unit 1 a. Steam Generator Blowdown Process Radiation Monitors b. Steam Generator Blowdown Line Flow Rate Monitors c. Containment Fan Coil Unit Process Radiation Monitors d. Plant Vent Radiation Monitoring System -Noble Gas, Iodine, Particulate, Flow Rate, and Sample Flow Rate Monitors e. Liquid Radwaste Disposal Process Radiation Monitor 10 I I I I I I I I I I I I I I :. I PART I. PART J. PART K.
  • Salem Unit 2 a. Steam Generator Blowdown Process Radiation Monitors b. Steam Generator Blowdown Line Flow Rate Monitors c. Containment Fan Coil Unit Process Radiation Monitors d. Plant Vent Radiation Monitoring System -Noble Gas, Iodine, Particulate, Flow Rate, and Sample Flow Rate Monitors e. Liquid Radwaste Disposal Process Radiation Monitor f. Chemical Waste Basin Process Radiation Monitor The Radiation Monitoring system instrumentation listed above have been inoperable during this report period due to the extended maintenance outage on Salem Unit 1 & 2. The Unit's have been shutdown since the 2nd quarter of 1995. Maintenance items conducted during this time period include the complete replacement of the Unit 1 and 2 Plant Vent Radiation Monitoring System; the replacement of Unit 1 Steam Generators, and extensive maintenance on the Unit 2 Waste Gas monitoring system. Additionally, the inability to establish sample stream flow due to the extended outage prevented restoring some of the radiation monitors to service. PROCESS CONTROL PROGRAM (PCP) CHANGES During this reporting period, there were no changes to the Process Control Program. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, there were no changes to the environmental monitoring sampling program. MAJOR CHANGES TO WASTE PROCESSING SYSTEMS During this reporting period, there were no major changes to the waste processing systems at Salem Unit 1 or 2. Although not considered a major change, an filtration

(<0.05u) unit was installed at Salem to process liquid radwaste during this time period. This unit is expected to reduce the amount of radioactivity released from Salem Units 1 and 2. 11 I I I I I I I I I I I .I I I SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. 1st Quarter 2nd Total A. Fission and Activation Gases Units 1. Total release Ci 0.00E+OO 2. Average release rate for period uCi/sec 0.00E+OO 3. Percent of technical specification limit (T.S. 3.11.2.2(a))

% B. Iodines 1. Total Iodine-131 Ci 2. Average release rate for period uCi/sec 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))

C. Particulates

1. Particulates with 9-0 half-lives

>8 days Ci 2. Average release rate for period uCi/sec 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))

% 4. Gross alpha Ci C. Tritium 1. Total Release Ci 2. Average release rate for period uCi/sec 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))

9-0 0.00E+OO 0.00E+OO O.OOE+OO 6.48E-04 O.OOE+OO O.OOE+OO 6.48E-04 O.OOE+OO 2.39E+Ol 3.04E+OO 6.48E-04 Quarter Error % 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO l.20E-03 7.lOE-07 9.02E-08 l.20E-03 O.OOE+OO 3.51E+Ol 4.46+00 l.20E-03 25 25 25 25 (1) For batch releases the estimated overall error is within 10% (2) Iodine, tritium and particulates are treated as a group 12 I I I I I I I I I I I I :. I SALEM GENERATING STATION TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and Activation Gases Units 1st Quarter 1. Total release Ci O.OOE+OO 2. Average release rate for period uCi/sec O.OOE+OO 3. Percent of technical specification limit (T.S. 3.11.2.2(a))

B. Iodines % O.OOE+OO 1. Total Iodine-131 Ci O.OOE+OO 2. Average release rate for period uCi/sec O.OOE+OO 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))

% 9.19E-04 C. Particulates

1. Particulates with half-lives

>8 days Ci 2. Average release rate for period uCi/sec 3. Percent of technical specification limit (2) (T.S. 3.11.2.3(a))

% 4. Gross alpha Ci C. Tritium 1. Total Release Ci 2. Average release rate for period uCi/sec 3. Percent of technical specification limit (2) (T.S. 3.ll.2.3(a))

% O.OOE+OO O.OOE+OO 9.19E-04 O.OOE+OO 3.39E+Ol 4.31E+OO 9.19E-04 2nd Quarter O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.14E-04 1.77E-06 2.25E-07 9.14E-04 O.OOE+OO 3.35E+Ol 4.26E+OO 9.14E-04 Est. Total Error % 25 25 25 25 (1) For batch releases the estimated overall error is within 10% (2) Iodine, tritium and particulates are treated as a group 13 I I I I I I I I I I I I I I SALEM GENERATING STATION TABLE 1B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1. Fission Gases 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter No fission gases were released during this report period. 2. Iodines No iodines were released during this report period. 3 . Particulates (half-live

>8 days) Cobalt-60 Ci O.OOE+OO 7.10E-07 O.OOE+OO O.OOE+OO Hydrogen-3 Ci 2.39E+01 3.51E+01 0.00E+OO O.OOE+OO TOTALS Ci 2.39E+01 3.51E+01 O.OOE+OO O.OOE+OO 14 I I I I I I I I I I I I I I I I SALEM 0ENERATING STATION TABLE 1B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1. Fission Gases 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter No fission gases were released during this report period 2. Iodines No iodines were released during this report period 3 . Particulates (half-lives

>8 days) Hydrogen-3 Ci 3.39E+01 3.35E+01 O.OOE+OO O.OOE+OO Cobalt-60 Ci 0.00E+OO 1.77E-06 O.OOE+OO O.OOE+OO TOTALS Ci 3.39E+01 3.35E+01 O.OOE+OO O.OOE+OO 15 I I I I I I I I I I I I I I I I I I SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter There were no ground level gaseous releases during this reporting period. 16 2nd Quarter I I I I I I I I 1* I I I I I I I I I .. SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. 1st Quarter 2nd Total A. Fission and activation products 1. Total release (not including tritium, Units gases, alpha) Ci 2. Average diluted concentration during period uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.2. (a)) B. Tritium Q. 0 1. Total release Ci 2. Average diluted concentration during period uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.1)

% C. Dissolved and entrained noble gases 1. Total release Ci 2. Average diluted concentration during period uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.1)

D. Gross alpha activity 1. Total release E. Volume of waste release (prior to dilution -% Ci 1.26E-01 2.57E-07 3.05E+OO 3.90E+OO 7.94E-06 2.65E-01 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO Batch Release) liters 3.16E+05 F. Volume of dilution water used during entire period liters 2.08E+10 17 Quarter Error % 1.54E-02 25 9.31E-08 3.40E-01 1.36E+OO 25 8.24E-06 2.75E-01 0.00E+OO 25 O.OOE+OO 0.00E+OO O.OOE+OO 25 1.27E+05 25 2.73E+10 25 I I I I I I I I 1* I I I I I I :-I -r SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and activation products 1. Total release (not including tritium, Units gases, alpha) Ci 2. Average diluted concentration during period uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.2.(a))

B. Tritium 1. Total release 2. Average diluted concentration during period 3. Percent of technical specification limit (T.S. 3.11.1.1)

C. Dissolved and entrained noble gases 1. Total release 2. Average diluted concentration during period 3. Percent of technical specification limit (T.S. 3.11.1.1)

D. Gross alpha activity 1. Total release E. Volume of waste release (prior to dilution -% Ci uCi/mL 9-0 Ci uCi/mL % Ci 1st Quarter 7.33E-02 l.80E-07 l.66E+OO 3.69E+OO 9.07E-06 3.02E-01 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Batch Release) liters 3.07E+05 F. Volume of dilution water used during entire period liters 8.55E+l0 18 Est. 2nd Total Quarter Error % 2.17E-02 25 8.18E-08 3.65E-01 4.43E+OO 25 l.67E-05 5.56E-01 O.OOE+OO 25 O.OOE+OO O.OOE+OO O.OOE+OO 25 l.86E+05 25 l.05E+ll 25 I I .. I I I I I I

  • I I I I I I I SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL JANUARY -JUNE 1997 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE 1st 2nd Nuclides Released Unit Quarter Quarter A. Fission Products Manganese-54 Ci O.OOE+OO O.OOE+OO Iron-55 Ci 0.00E+OO 0.00E+OO Cobalt-57 Ci 0.00E+OO O.OOE+OO Cobalt-58 Ci 0.00E+OO 0.00E+OO Cobalt-60 Ci O.OOE+OO O.OOE+OO Strontium-90 Ci 0.00E+OO O.OOE+OO Niobium-97 Ci O.OOE+OO O.OOE+OO Silver-110m Ci O.OOE+OO O.OOE+OO Antimony-125 Ci O.OOE+OO O.OOE+OO Cesium-134 Ci O.OOE+OO O.OOE+OO Cesium-137 Ci O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO O.OOE+OO B. Tritium, Dissolved and Entrained Gases Hydrogen-3 Ci 0.00E+OO O.OOE+OO TOTALS Ci 0.00E+OO O.OOE+OO 19 REPORT BATCH MODE 1st 2nd Quarter Quarter 1.13E-03 2.21E-04 1.61E-02 O.OOE+OO 7.95E-05 2.33E-05 7.51E-04 1.97E-05 1.61E-02 2.SOE-03 3.48E-05 O.OOE+OO 7.43E-05 O.OOE+OO 7.30E-04 0.00E+OO 3.04E-03 1.42E-03 2.71E-02 3.20E-03 6.10E-02 8.01E-03 l.26E-01 1.54E-02 3.90E+OO 1.36E+OO 3.90E+OO 1.36E+OO

I SALEM GENERATING STATION I TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -JANUARY -JUNE 1997 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE I 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter I A. Fission Products I Manganese-54 Ci O.OOE+OO 0.00E+OO 8.58E-04 7.37E-04 Iron-55 Ci O.OOE+OO 0.00E+OO 1.30E-02 O.OOE+OO Cobalt-57 Ci O.OOE+OO O.OOE+OO 7.64E-05 4.72E-05 I Cobalt-58 Ci 0.00E+OO O.OOE+OO 4.53E-04 1.55E-04 Cobalt-60 Ci O.OOE+OO O.OOE+OO 1.33E-02 9.79E-03 Strontium-90 Ci 0.00E+OO O.OOE+OO 2.71E-05 O.OOE+OO I Niobium-97 Ci O.OOE+OO O.OOE+OO 1.70E-05 O.OOE+OO Silver-110m Ci O.OOE+OO O.OOE+OO 3.20E-04 O.OOE+OO Antimony-125 Ci O.OOE+OO O.OOE+OO 2.86E-03 1.97E-03 Cesium-134 Ci 0.00E+OO O.OOE+OO 1.31E-02 2.49E-03 I Cesium-137 Ci O.OOE+OO O.OOE+OO 2.94E-02 6.54E-03 TOTALS Ci O.OOE+OO O.OOE+OO 7.33E-02 2.17E-02 B. Tritium, Dissolved and Entrained Gases I Hydrogen-3 Ci O.OOE+OO 0.00E+OO 3.69E+OO 4.43E+OO I TOTALS O.OOE+OO 0.00E+OO 3.69E+OO 4.43E+OO I I I I ':. I 20 I I I I I I I I 1e I I I I I I :. I 1 ' SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total 1. Type of waste Units(l) period Error, S). 0 a. Spent resins, filters, m3 0.00E+OO sludges, evaporator bottoms Ci 0.00E+OO 25 b. Dry compressible waste, m3 2.26E+Ol contaminated equipment.

Ci 4.40E-01 25 c. Irradiated components, m3 O.OOE+OO control rods Ci O.OOE+OO 25 d. Others (described) m3 5.80E+02 Steam Generators (3) Ci 3.55E+02 25 2. Estimate of major nuclide composition (for Type A and B waste) DAW Steam Generators

(%) (Ci) (%) (Ci) Iron-55 44.0 0.19 40.6 144.1 Nickel-63

21. 8 0.10 9.1 32.3 Cesium-137 13.5 0.06 N/A N/A Cobalt-60
11. 9 0.05 49.0 174.0 Cesium-134 5.2 0.02 N/A N/A Cobalt-58
1. 4 0.01 N/A N/A Silver-llOm
1. 3 0.01 N/A N/A Manganese-54 N/A N/A 1. 3 4.6 21 I I I I I I I I I I I I I I I I
  • t 3 . SALEM GENERATING STATION TABLE 3 (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Disposition Number of Shipments 6 3 Mode of Transportation Truck Truck, Barge Type of Destination Containers Oak Ridge, Tn Strong, Tight Containers Barnwell, S.C. DOT-E-11745 (IP-2) Note: No solidification agents were used during this reporting period. 4. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments None Mode of Transportation N/A 22 Destination N/A I I ,, I I I I I I

  • I I I I I I :. I I ' SALEM GENERATING STATION TABLE 4A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. 2. 3. 4 . 5. 6. 7 . 8 . Dates: January 1 -March 31, 1997 Type of release: Gas Number of releases during the 1st Quarter: 0 Total time duration for all releases of type listed above: O.OOE+OO minutes Maximum duration for release of type listed above: O.OOE+OO minutes Average duration for release of type listed above: 0.00E+OO minutes Minimum duration for release of type listed above: O.OOE+OO minutes Average stream flow (dilution flow) during the period of release: N/A 23 I I -I I I I I I 19 I I I I I I I . " SALEM GENERATING STATION TABLE 4A-l (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. Dates: April 1 -June 30, 1997 2. Type of release: Gas 3. Number of releases during the 2nd Quarter: 0 4 . 5. 6. 7 . 8 . Total time duration for all releases of type listed above: O.OOE+OO minutes Maximum duration for release of type listed above: O.OOE+OO minutes Average duration for release of type listed above: O.OOE+OO minutes Minimum duration for release of type listed above: 0.00E+OO minutes Average stream flow (dilution flow) during the period of release: N/A 24 I I I I I I I I

  • I I I I I I :. I ' ,, .l SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. Dates: January 1 -March 31, 1997 2 . Type of release: Gas 3. Number of releases during the 1st Quarter: 16 4. Total time duration for all releases of type listed above: 3.66E+03 minutes 5. Maximum duration for release of type listed above: l.08E+03 minutes 6. Average duration for release of type listed above: 2.29E+02 minutes 7. Minimum duration for release of type listed above: l.07E+02 minutes 8. Average stream flow (dilution flow) during the period of release: N/A 25 I I ,, I I I I I I 19 I I I I I I I ' 1; SALEM GENERATING STATION TABLE 4A-2 (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. 2. 3 . 4 . 5. 6. 7 . 8 . Dates: April 1 -June 30, 1997 Type of release: Gas Number of releases during the 2nd Quarter: 14 Total time duration for all releases of type listed above: 3.42E+03 minutes Maximum duration for release of type listed above: l.35E+03 minutes Average duration for release of type listed above: 2.44E+02 minutes Minimum duration for release of type listed above: 1.50E+02 minutes Average stream flow (dilution flow) during the period of release: N/A 26 I ... SALEM GENERATING STATION TABLE 48-1 I ,, I I I I I I I I I I I I :. I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. 2. 3 . 4. 5. 6. Dates: January 1 -March 31, 1997 Type of release: Liquid Number of releases during the 1st Quarter: 5 Total time duration for all releases of type listed above: 1.30E+03 minutes Maximum duration for release of type listed above: 3.05E+02 minutes Average duration for release of type listed above: 2.60E+02 minutes 7. Minimum duration for release of type listed above: 2.07E+02 minutes 8 . Average stream flow (dilution flow) during the period of release: 1.00E+05 gpm 27 I I I I I I I I

  • I I I I I I :. I f 'I SALEM GENERATING STATION TABLE 4B-1 (CONT'D) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1. 2. 3 . 4 . 5. 6 . 7. 8 . Dates: April 1 -June 30, 1997 Type of release: Liquid Number of releases during the 2nd Quarter: 2 Total time duration for all releases of type listed above: 4.37E+02 minutes Maximum duration for release of type listed above: 2.32E+02 minutes Average duration for release of type listed above: 2.19E+02 minutes Minimum duration for release of type listed above: 2.05E+02 minutes Average stream flow (dilution flow) during the period of release: 1.00E+05 gpm 28 I I -I I I I I I 19 I I I I I I I .. SALEM GENERATING STATION TABLE 4B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. 2 . 3 . 4 . 5. 6. 7 . 8 . Dates: January 1 -March 31, 1997 Type of release: Liquid Number of releases during the 1st Quarter: 5 Total time duration for all releases of type listed above: 1.07E+03 minutes Maximum duration for release of type listed above: 2.48E+02 minutes Average duration for release of type listed above: 2.15E+02 minutes Minimum duration for release of type listed above: 1.95E+02 minutes Average stream flow (dilution flow) during the period of release: 1.00E+05 gpm 29 I I I I I I I I I I I I I I I ' 'I .1 SALEM GENERATING STATION TABLE 4B-2 (CONT ID) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -JUNE 1997

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY 1. 2 . 3 . 4 . 5. Dates: April 1 -June 30, 1997 Type of release: Liquid Number of releases during the 2nd Quarter: 3 Total time duration for all releases of type listed above: 7.02E+02 minutes Maximum duration for release of type listed above: 2.80E+02 minutes 6. Average duration for release of type listed above: 2.34E+02 minutes 7. 8 . Minimum duration for release of type listed above: 1.98E+02 minutes Average stream flow (dilution flow) during the period of release: 1.00E+05 gpm 30 I . ,, I I 1* I I I I I I I ,. I I ). I AMENDMENT TO RERR -41 I I I I I I I I I I I I I . ' SALEM GENERATING STATION TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1996 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and activation products 1. Total release (not including tritium, Units gases, alpha) Ci 2. Average diluted concentration during period of release uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.2.(a))

% B. Tritium 1. Total release Ci 2. Average diluted concentration during period uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.1)

% C. Dissolved and entrained noble gases 1. Total release Ci 2. Average diluted concentration during period uCi/mL 3. Percent of technical specification limit (T.S. 3.11.1.1)

% 3rd Quarter 1.59E-02 3.84E-08 3.lOE-01 1.35E+OO 3.25E-06 1.08E-01 O.OOE+OO O.OOE+OO O.OOE+OO D. Gross alpha activity 1. Total release Ci 0.00E+OO E. Volume of waste release (prior to dilution -Batch Release) F. Volume of dilution water liters 2.46E+05 used during entire period liters 9.99E+09 19 Est. 4th Total Quarter Error % 2.24E-02 25 5.05E-08 4.96E-01 3.74E+OO 25 8.44E-06 2.81E-01 0.00E+OO 25 0.00E+OO O.OOE+OO 0.00E+OO 25 2.48E+05 25 1.12E+l0 25 I I I I I I I I I I I I* I I I I * -( u ,; SALEM GENERATING STATION TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1996 UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. 3rd Quarter 4th Total A. Fission and activation products 1. Total release (not including tritium, Units gases, alpha) Ci 8.62E-02 2. Average diluted concentration during period uCi/mL 5.43E-08 3. Percent of technical specification limit (T.S. 3.11.1.2. (a)) % 2.58E+OO B. Tritium 1. Total release Ci l.06E+Ol 2. Average diluted concentration during period uCi/mL 6.69E-06 3. Percent of technical specification limit (T.S. 3.11.1.1)

% 2.23E-01 C. Dissolved and entrained noble gases 1. Total release Ci O.OOE+OO 2. Average diluted concentration during period uCi/mL 0.00E+OO 3. Percent of technical specification limit (T.S. 3.11.1.1)

% O.OOE+OO D. Gross alpha activity 1. Total release Ci O.OOE+OO E. Volume of waste release (prior to dilution -Batch Release) liters 7.94E+05 F. Volume of dilution water used during entire period liters 7.llE+lO 20 Quarter Error 2.27E-02 25 8.lOE-08 5.38E-01 2.51E+OO 25 8.97E-06 2.99E-01 0.00E+OO 25 0.00E+OO 0.00E+OO O.OOE+OO 25 1.87E+05 25 4.31E+10 25 I I I I I I I I I I I I I* I I I

  • f * .. SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1996 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Manganese-54 Ci 0.00E+OO O.OOE+OO 2.54E-04 1.22E-04 Iron-55 Ci 0.00E+OO O.OOE+OO 4.19E-04 4.22E-04 Cobalt-57 Ci O.OOE+OO 0.00E+OO 2.39E-05 3.49E-05 Cobalt-58 Ci 0.00E+OO O.OOE+OO 4.46E-04 3.0lE-04 Cobalt-60 Ci 0.00E+OO O.OOE+OO 4.81E-03 5.37E-03 Strontium-90 Ci O.OOE+OO 0.00E+OO 6.41E-05 4.71E-05 Silver-llOm Ci O.OOE+OO O.OOE+OO 1.46E-05 O.OOE+OO Antimony-125 Ci O.OOE+OO 0.00E+OO l.50E-03 1.22E-03 Cesium-134 Ci O.OOE+OO O.OOE+OO 2.63E-03 4.57E-03 Cesium-137 Ci O.OOE+OO O.OOE+OO 5.79E-03 1.03E-02 ------------------------------------------------------------------

TOTALS Ci O.OOE+OO O.OOE+OO 1.59E-02 2.24E-02 Tritium Ci O.OOE+OO 0.00E+OO 1.35E+OO 3.74E+OO TOTALS Ci 0.00E+OO 0.00E+OO 1.35E+OO 3.74E+OO 21 I I I I I I I I I I I I I I I I SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -DECEMBER 1996 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH 3rd 4th 3rd Nuclides Released Unit Quarter Quarter Quarter Manganese-54 Ci O.OOE+OO O.OOE+OO 9.81E-04 Iron-55 Ci 6.99E-04 O.OOE+OO l.04E-02 Cobalt-57 Ci O.OOE+OO O.OOE+OO l.51E-04 Cobalt-58 Ci O.OOE+OO O.OOE+OO 2.46E-03 Cobalt-60 Ci O.OOE+OO O.OOE+OO 3.13E-02 Zinc-65 Ci 0.00E+OO O.OOE+OO l.35E-04 Strontiurn-90 Ci l.15E-05 O.OOE+OO l.71E-04 Silver-llOrn Ci O.OOE+OO 0.00E+OO l.73E-03 Antirnony-125 Ci O.OOE+OO O.OOE+OO 6.98E-03 Cesiurn-134 Ci O.OOE+OO O.OOE+OO 9.SlE-03 Cesiurn-137 Ci 3.50E-06 O.OOE+OO 2.13E-02 MODE 4th Quarter 9.26E-05 7.46E-04 l.12E-05 l.90E-04 4.12E-03 0.00E+OO 4.48E-05 O.OOE+OO 8.38E-04 5.20E-03 l.15E-02 ------------------------------------------------------------------

TOTALS Ci 7.14E-04 O.OOE+OO 8.55E-02 2.27E-02 Tritium Ci O.OOE+OO O.OOE+OO l.06E+Ol 2.51E+OO ---------------------------------------------------------------

TOTALS O.OOE+OO O.OOE+OO 1.06E+Ol 2.51E+OO 22

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